ML20027B148
| ML20027B148 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/07/1982 |
| From: | Tucker H DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8209160481 | |
| Download: ML20027B148 (2) | |
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i Duxis Powntu Gonnw.w I'.O. IM)X !!!!!80 CIIAHl.OTTE, N.C. 28242 IIAL 15. TUGKEH m erisome (704) il7'l-45'll Tla.El permeDENT hgtl. FAN raastMid Tisps September 7, 1982 Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission l
Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re: Catawba Nuclear Station Units 1 and 2 Docket Nos. 50-416 and -414 1
2
Dear Mr. O'Reilly:
Pursuant to 10 CFR 50.55e, please find attached an update to Significant Deficiency j
Report IE 78/02-SPS-413/414.
i Very truly yours, lh f
1 l
Hal B. Tucker RWO/php Attachment cc: Director Mr. Robert Guild, Esq.
l Office of Inspection & Enforcement Attorney-at-Law U. S. Nuclear Regulatory Commission 314 Pall Mall f
Washington, D. C. 20555 Columbia, South Carolina 29201 Mr. P. K. Van Doorn Palmetto Alliance l
NRC Resident Inspector 2135 Devine Street Catawba Nuclear Station Columbia, South Carolina 29205 l.
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o DUKE POWER COMPANY CATAWBA NUCLEAR STATION SIGNIFICANT DEFICIENCY Report No:
IE 78/02-SPS-413/414 Progress Report Date:
September 7, 1982 Facility: Catawba Nuclear Station, Units 1 & 2 Identification of Deficiency:
Cafety Related Containment Isolation Valve Type C Leakage Deficiency Initial Report:
An initial formal written report (IE78/02-5PS-413/414 dated September 19, 1978) was provided to the NRC on this deficiency.
Description of Deficiency:
During preliminary seat leakage air testing of hard seat containment isolation valves, actual valve seat air leakage exceeded Type C containment isolation valve leakage criteria. Low air pressure valve seat leakage testing similar to contain-ment Type C leakage testing was not a requirement of applicable Duke valve pro-curement specifications.
Analysis of Safety Implications:
Had this deficiency not been identified and requirements of 10 CFR 50 Appendix J imposed, overall containment isolation leakage allowables would have been exceeded.
Corrective Action:
Duke document DCA-MEQP-0004 identifies all af fected valves and corrective action /
modifications required to be done by Catawba Construction Department. Design Engineering corrective action is complete. Modifications made were:
(1) For some of the affected gate valves, a seal water system (System NW) was added.
The purpose of the seal water system is to eliminate air leakage through the gate valve by sealing valve body with water at higher pressure than containment accident pressure.
(2) For other affected containment isolation valves, the valves were either modified or replaced to obtain valves with elastomeric seating materials. The effect of replacing metal valve seats by clastomeric seats results in reduction of seat leakage to acceptable limits. Acceptable seat leakage tests were performed by the manufacturers of replacement valves and by manufacturers of valves modified by manufacturer. All replacement valves and valve parts have been delivered to the site.
Remaining valve modifications are Kerotest valves to be modified from metal seated design to elastomeric seated design. Due to Construction schedule most of the Kerotest valves will be modified af ter valves are installed in piping.
Some valves have internals removed to avoid clogging and damage during piping flush and hydro. For the above reasons, the seat leakage tests of modified Kerotest valves will be preliminary Type C tests performed by Nuclear Production Department after system turnover.
Rev. 1 A